ML20065C275
| ML20065C275 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/27/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065C276 | List: |
| References | |
| NUDOCS 8209230302 | |
| Download: ML20065C275 (13) | |
Text
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VIRGIL C. SUMMER HUCLEAR STATION, UNIT HO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Ho. 2 License No. HPF-12 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment to the Virgil C. Summer Nuclear Stdtion, Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated August 13, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the appifcation, as amended, the provisions of the Act, and the regulations of i
the Commission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations
'st set forth in 10 CFR Chapter I; 0.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is hereby amended by page changes to the
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Technical Specifications as indicated in tne attachments to this i
license amendment. Paragraph 2.C(2) of Facility Operating License (1
i No. NPF-12 is hereby amended to read as follows:
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(2) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, are hereby incorporated into this license.
South Carolina Electric & Gas Company shall operate tne facilit;/
1 in accordance with the Technical Sneci fications and the env i rn nran t al Protection Plan.
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6209230302 B20B27 PDR ADOCK 05000395 P
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0FNISSION Original signed by: ~
WilliamKane Y
B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance:
AUG 2 71982
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REFUELING OPERATIONS l
3/4.9.9 WATER LEVEL - REFUELING CAVITY AND FUEL TRANSFER CANAL LIMITING CONDITION FOR OPERATION
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3.9.9 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.
APPLICABILITY:
During movemen's of fuel assemblies or control rods within the reactor pressure vessel or the refueling cavity when either the fuel assemblies being moved or the fuel assemblies seated within the reactor pressure vessel are irradiated.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within'the pressure vessel.
SURVEILLANCE REQUIREMENTS 4.9.9 The water level shall be determined to be at least its minimum re, quired depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereaf ter during movement of fuel assemblies or control rods.
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SUMMER - UN.IT._1, 3/4 9-10 f
REFUELING OPERATIONS 3/4.9.8 REACTOR BUILDING PURGE SUPPLY AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.8 The Reactor Building Purge Supply and Exhaust Isolation System shall be OPERABLE.
APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
With the' Reactor Building Purge Supply and E'xhaust Is.olation System inoperable,"
close each of the Purge and Exhaust penetrations providing direct access from the reactor building atmosphere to the outside atmosphere.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.8 The Reactor Building Purge Supply and Exhaust Isolation System shall be.
demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERNATIONS by verifying that Reactor Building Purge Supply and Exhaust isolation occurs on manual initiation and on a high radiation test signal from each of the containment radiation monitoring instrumentation channels, and by verifying that isolation occurs on the 36-inch lines of the Purge Supply and Exhaust Isolation System on a high radiation test signal from the reactor building manipulator crane area channels.
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SUMMER - UNIT 1 3/4 9-9 Amendment ha. 2
E TABLE 3.8-1 k
I CONTAINMENTPENETRATIONCONDUCTdROVERCURRENTPROTECTIVEDEVICETESTSETPOINTCRITERIA C5
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EQUIP N0.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME 7.2 KV Swgr.
1)
XPP0030A-RC PRIMARY XSW1A #9 LONG TIME 3960 Amps
< 15.75 Sec.
Reactor Coolant Pump A INSTANT 5808 Amps N/A GROUND INST. 11 Amps N/A BUS 1A Normal Feed BACKUP XSW1A #5 LONG TIME 5544 Amps
< 15.33 Sec.
BUS 1A Emergency Feed BACKUP XSW1A #3 LONG TIME 5544 Amps 15.33 Sec.
2)
XPP0030B-RC PRIMARY XSW1B #7 LONG TIME 3690 Amps
< 15.75 Sec.
w1 Reactor Coolant Pump B INSTANT 5808 Amps N/A GROUND INST. 11 Amps N/A 9
5 BUS 1B Normal Feed
. BACKUP XSW1B #5 LONG TIME 5544 Amps
< 15.33 Sec.
BUS 1B Emergency Feed BACKUP XSW1B #3 LONG TIME 5544 Amps 315.33Sec.
3)
XPP0030C-RC PRIMARY XSW1C #3 LONG TIME 3960 Amps
< 15.75 Sec.
Reactor Coolant Pump C INSTANT 5808 Amps N/A GR0VHD INST. 11 Amps N/A BUSIC Normal Feed BACKUP XSW1C #9 LONG TIME 5544 Amps
< 15.33 Sec.
BUSIC Emergency Feed BACKUP XSW1C #13 LONG TIME 5544 Amps 515.33Sec.
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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
2.
By selecting and functionally testing.a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functicnal testing shall be selected on a rotating basis.
Testing of these circuit breakers shall consist of injecting a current in excess of the breakers nominal setpoint and measuring the response time.
The measured response time will ba compared to the manufacturer's data to insure that it is less than or equal to a value specified by the manufacturer.
Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional repre-sentative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
3.
By selecting and functionally testing a representative sample of each type of fuse on a rotating basis.
Each representative sample of fuses shall include at least 10% of all fuses of that type. The functional test shall consist of a non-destructive resistance measurement test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found inoperable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommentations.
SUMMER - UNIT 1 3/4 8-17
TABLE 3.3-12 4
E RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION c:
!)
MINIMUM g
CHANNELS INSTRUMENT OPERABLE ACTION s,
1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line - RM-L5 or RM L9 1
31 b.
Nuclear (Processed Steam Generator) Blowdown Effluent 1
32 Line RM-L7 or RM-L9 c.
Steam Generator Blowdown Effluent Line 1.
Unprocessed during Power Operation - RM-L10 or RM-L3 1
32
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2.
Unprocessed during Startup - RM-L3 1
32 d.
Turbine Building Sump Effluent Line - RM-L8 1
33 2.
FLOW RATE MEASUREMENT DEVICES
- a.
Liquid Radwaste Effluent Line - Tanks 1 and 2 1/ tank 34 b.
Penstocks Minimum Flow Interlock **
1 34 c.
Nuclear Blowdown Effluent Line 1
34 d.
Steam Generator (Unprocessed) Blowdown Effluent Line 1
34 3.
TANK LEVEL INDICATING DEVICES
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a.
Condensate Storage Tank 1
35 8
m
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- Flow rate for the monitor RM-L9 is determined by adding flow rates for monitors RM-L5 and RM-L7.
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- Minimum dilution flow is assured,by an interlock teruinating liquid waste releases if minimum dilution flow is not available.
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t INSTRUMENTATION RADIOACTIVE LIQUID' EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channelt.
shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm /
trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM).
APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid' effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than t.he minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.
Additionally if this condition prevails for more than 30 days, in the next semiannual effluent report, explain why this condition was not.orrected in a timely manner.
c.
The provisions of Specifications 6.9.1.12.b, 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel siall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-8.
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SUMMER - UNIT 1 3/4 3-67
TABLE 3.3-4 (Continued) 4 E3 ENGINEERED SAFETY' FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g
Total l
q Functional Unit Allowance (TA)
Z S
Trip Setpoint Allowable Value 3.
. CONTAINMENT ISOLATION
- a., Phase "A" Isolation 1.
Manual NA NA NA NA NA 2.
Safety Injection See 1 above for all safety injection setpoints and allowable values 3.
Automatic Actuation Logic NA NA NA NA NA and Actuation Relays
.b.
Phase "B" Isolation 1.
Automatic Actuation NA NA NA NA NA I
Logic and Actuation
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Relays h
2.
Reactor Building 3.0 0.71 1.5
$12.05 psig
$12.31 psig Pressure-High 3 c.
Purge and Exhaust Isolation 1.
Safety Injection See 1 above for all safety injection setpoints and allowable values 2.
Containment Radioactivity NA NA NA High 3.
Automatic Actuation NA NA NA NA NA 2I Logic and Actuation
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Relays R
E
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- Trip setpoints shall be set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
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TABLE 3.3-4 m
7 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E
Total
- Z Functional Unit Allowance (TA)
Z_
S_
Trip Setpoint Allowable Value
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1.
SAFETY INJECTION, REACTOR TRIP, l
FEEDWATER ISOLATION, CONTROL
.c ROOM ISOLATION, START DIESEL GENERATORS, CONTAINMENT COOLING FANS AND ESSENTIAL SERVICE WATER.
a.
Manual Initiation NA NA NA NA NA b.
Automatic Actuation Logic NA NA NA NA NA w
c.
Reactor Building Pressure-3.0 0.71 1.5 13.6 psig 13.86 psig 1
High 1 y
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Pressurizer Pressure--Low 13.1 10.71 1.5 11850 psig 11839 psig e.
Differential Pressure 3.0 0.87 1.5/
197 psig
$106 psi Between Steamlines--High 1.5 f.
Steamline Pressure--Low 20.0 10.71 1.5 1675 psig 1635 psig(1) 2.
REACTOR BUILDING SPRAY a.
Manual Initiation NA NA NA NA NA b.
Automatic Actuation Logic NA NA NA NA NA and Actuation Dr. lays c.
Reactor Building Pressure-3.0 0.71 1.5
$12.05 psig
$12.31 psig l
High 3 (Phase 'A' isolation aligns spray system dis-charge valves and NaOH tank suction valves)
(1) Time constants utilized in lead lag controller for steamline pressure-low are as follows ti 1 50 secs.
T2 1 5 secs.
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TABLE 3.3-3 (Continued) 39 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION t
C
- i MINIMUM
,' -d TOTAL NO.
CHANNELS CHANNELS APPLICABLE H
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 3.
CONTAINMENT ISOLATION a.
Phase "A" Isolation 1)
Manual 2
1 2
1,2,3,4 18 2)
Safety Injection See 1 above for all safety injection initiating' functions and requirements.
3)
Automatic Actuation Logic and Actuation Relays 2
1 2
1,2,3,4 14 to 32 b.
Phase "B" Isolation T
1)
Automatic Actuation 2
1 2
1,2,3,4 14 Logic and Actuation Relays 2)
Reactor Building 4
2 3
1,2,3 16 Pressure--High-3 c.
Purge and Exhaust Isolation 1)
Safety Injection See 1 above for all safety injection initiating functions and requirements.
2)
Containment Radio-2 I
2 1,2,3,4 17 k'
activity-High g
3)
Automatic Actuation 2
1 2
1,2,3,4 17 g
Logic and Actuation Relays
=
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IE TABLE 3.3-3 (Continuedl I
ES ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION C
35 MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION f,.
Steam Line Pressure-Low 1 pressure /
1 pressure 1 pressure 1,2,3 19*
loop and 2 loops and 2 loops 2.
REACTOR BUILDING SPRAY a.
Manual 2 sets - 2 1 set 2 sets 1,2,3,4 18 switches / set ti b.
Automatic Actuation 2
1 2
1,2,3,4 14 Logic and Actuation
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Relays u
c.
Reactor Building 4
2 3
1, 2, 3 16 Pressure--High-3 (Phase 'A' isolation aligns spray system discharge valves and NaOH tank suction valves) 1 9
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t ATTACHPENT TO LICENSE AMENDMEHT NO. 2 i
FACILITY OPERATING LICENSE NO. NPF-12 4
DOCKET NO. 50-395 i
Replace the following pages of the Appendix "A" Technical Specifications I
with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of the changes.
Amended Page 3/4 3-18 3/4 3-26 3/4 3-68 3/4 8-18 3/4 9-9 1
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